IR 05000269/1978035

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IE Insp Repts 50-269/78-35,50-270/78-33 & 50-287/78-35 on 781211-14.No Noncompliance Noted.Major Areas Inspected: Licensee Event Repts,Visual Insp of Snubbers,Housekeeping & Cleanliness of Reactor Bldgs
ML15223A415
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/17/1979
From: Bewis R, Brooks E, Jape F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML15223A412 List:
References
50-269-78-35, 50-270-78-33, 50-287-78-35, NUDOCS 7902150437
Download: ML15223A415 (5)


Text

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UNITED STATES o

NUCLEAR REGULATORY COMMISSION o?

REGION II

X a101 MARIETTA STREET, X ATLANTA, GEORGIA 30303 Report Nos.: 50-269/78-35, 50-270/78-33 and 50-287/78-35 Docket Nos.: 50-259, 50-270 and 50-287 License Nos.: DPR-38, DPR-47 and DPR-55 Licensee: Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name:

Oconee 1, 2 and 3 Inspection at: Oconee Nuclear Station Inspection conducted:

December 11-14, 1978

. Inspector: F. Jape, December 11-14, 1978 E. H. Brooks, December 13, 1978 Approved by:_____

//22 R-

. Lewis, Chif 4/

Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on December 11-14, 1978 (Report Nos. 50-269/78-35, 50-270/78-33 and 50-287/78-35)

Areas Inspected:

Routine, unannounced inspection of licensee event reports, visual inspection of snubbers, housekeeping and cleanliness of Units 2 and 3 reactor buildings and review of incident investigation inde The inspection involved 38 inspector-hours onsite by two NRC inspector Results:

Of the four areas inspected, no items of noncompliance or devia tions were identifie RH Report Nos. 50-269/78-35, 50-270/78-33 and 50-287/78-35 I-1 DETAILS I Prepared by:

F. Jape, Resident Inspector fate Reactor Projects Section No. 2 Reactor Operations and Nuclear Support rans E7H. Brooks, Reactor Inspector Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: December 1 -14, 1978 Reviewed by:

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t'.

Lewis, Chief Date Reactor Projects Se tion No. 2 Reactor Operations and Nuclear Support Branch Persons Contacted

  • J. E. Smith, Station Manager
  • J. N. Pope, Superintendent of Operations
  • R. T. Bond, Licensing and Projects Engineer
  • D. J. Vito, Associate Engineer, Licensing
  • J. M. Davis, Superintendent of Maintenance T. D. Patterson, Shift Supervisor J. W. Herring, Shift Supervisor D. Thompson, Mechanical Maintenance Engineer J. Copeland, Maintenancee Coordinator B. Carney, Assistant Engineer, Mechanical Maintenance K. M. Koehler, Superintendent of Technical Services
  • Denotes those present at the exit intervie.

Licensee Actions on Previous Inspection Findings Not Inspecte.

Unresolved Items No new unresolved items were identifie RII Report Nos. 50-269/78-35, 50-270/78-33 and 50-287/78-35 1-2 Management Exit Meeting The inspector met with J. E. Smith and those denoted in Paragraph 1 at the conclusion of the inspection on December 14, 1978. The inspection findings were discussed and licensee management committed to report, by telephone on December 15, 1978, the results of snubber examination for Unit Other inspection findings were acknowledged without significant commen.

Review of Licensee Event Reports The inspector performed an in-office review of the non-routine event reports listed below to verify that the report details met license requirements, identified the cause of the event, described corrective actions appropriate for the identified cause, adequately assessed the event and any generic implication In addition while at the site, the inspector examined selected operating and maintenance logs and records, and internal incident investigation reports. Personnel were interviewed to verify that the report accurately reflected the circum stances of the event, that the corrective action had been taken or responsibility assigned to assure completion and that the event was reviewed by the licensee as stipulated in the Technical Specification The following event reports were reviewed:

RO - 270/78-11, ES Ch 3, RB Narrow Range Pressure Transmitter, Out-of Calibration RO - 269/78-11, ECCS Small Break Analysis Error RO -

269/78-24, Operation with OTSG Tubes Misplugged No items of noncompliance or deviations were identifie.

Incident Investigation Index A review of the incident investigation index was conducted to verify that investigations were performed and that events required to be reported to the NRC, were reporte The review covered forty events that occurred between August 23, 1978, to December 11, 197 There were no discrepancies identifie Questions regarding the reportability of three events were discussed with licensee personnel. Each question was resolved satisfactoril I No items of noncompliance or deviations were identifie RII Report Nos. 50-269/78-35, 50-270/78-33 and 50-287/78-35 1-3 Plant Tour A tour of accessible plant areas, including Units 2 and 3 Reactor Buildings, was conducte During the tour observations were made regarding plant housekeeping, cleanliness, ongoing activities, radia tion control practices and security practice Housekeeping and cleanliness were found to be satisfactory concerning the ongoing activities at the tim Security and radiation control practices, especially at the entrance to Units 2 and 3 Reactor Building were observed to be satisfactor Station Directive 3.11.4 specifies the controls necessary to maintain the appropriate level of cleanliness of open systems. During the tour of Unit 2 Reactor Building the inspector noted that these controls were being observed in and around the steam generators and reactor coolant pump repair No items of noncompliance or deviations were identifie. Inspection of Pipe Support and Restraint Systems During the period of November 27 - December 1, 1978, the inaccessible piping restraints (snubbers)

on Oconee, Unit 2 were inspecte At that time five inoperable snubbers were identified. As a follow-up to that inspection the inaccessible snubbers installed in Oconee, Unit 3 were inspected as reported herein. Accompanied by licensee personnel, the inspectors examined in excess of 50 percent of the inaccessible snubbers installed in Unit 3. The result of this inspection showed five snubbers with empty fluid reservoir These snubbers were removed by the licensee for functional testing of operability, and were dis assembled for examination of integral part The licensee also performed a 100% inspection of all inaccessible snubber No additional defective snubbers were foun The results of the functional tests (witnessed by inspector) showed all five snubbers to be operable and within specification. The cause of fluid leakage from the snubbers and the corrective action taken were as follows:

Snubber Cause of Leakage Corrective Action I

Nicked Seal Rebuild and Reinstall

Leaking Tube Fittings Replace

SRII Report Nos. 50-269/78-35, 50-270/78-33 and 50-287/78-35 1-4

Cracked Reservoir Replace

-Nicked Seal Replace

Worn Bushing and Piston Rod Replace Since the licensee functionally tested and demonstrated operability, identified the causes for the visual inspection failures, and corrected those causes, no change in the scheduled frequency of snubber inspection is required for Unit When questioned about the operability of the snubbers in Oconee, Unit 1, the licensee stated that an improved snubber cylinder (Miller Design) was used in Unit 1, and that this design has fewer fittings and a cup-type piston rod seal, which should provide more protection against fluid leakage. The licensee stated that all suppressors in Unit 1 are new and had been assembled at the vendor's plant, whereas the snubbers in Units 2 and 3 are older and had been disassembled at the site to replace all seals with ethylene propylene seal The licensee agreed to advise the NRC within 60 days of a plant outage to permit inspection of the installed inaccessible snubbers in Unit Based on our findings no change in inspection schedule will be required on Units 1 and 3. The schedule for inspection of Unit 2 inaccessible snubbers will be changed from 18 months to 2 months since the five snubbers found to be empty were not functionally tested in their as found condition, i.e., the fluid reservoirs were filled before testing and are of different desig No items of noncompliance or deviations were identified.